부산대학교 도서관

The Feinberg-Galanin method for heterogeneous reactors is formulated by using a two-group model rather than an age kernel. This treatment is then extended to take into account secondary effects, such as fast fission and thermalization of neutrons inside a rod which may contain moderator. The use of a single coefffcient in a FeinbergGalanin approach allows one to relate the source and sink strength of the fuel element to the thermal flux only. By defining a set of four coefficients, it is possible to connect the strengths of thermal- and fast-neutron sources and sinks to both thermal and fast fluxes. A method is presented for calculation of these four coefficients, alpha /sub 1/, BETA /sub 1/, alpha /s ub 2/, and BETA /sub 2/. (auth)